Eddy current for the characterization of broached tube support plate blockage

Abstract

A method for determining tube support plate blockage of a steam generator includes the following steps: measuring at least five different eddy current values per tube support intersection; calculating a nominal clean fit radius of flow hole; determining a center signal response; converting the center signal response to a deposit thickness; determine an edge reduction; converting the edge reduction to an edge thickness; calculating the resulting flow hole radius; verifying the reasonableness of the resulting flow hole radius; and determining a virtual calibration range.

Description

[0001]Priority to U.S. Provisional Patent Application Ser. No. 61 / 271,691 filed Jul. 24, 2009, is claimed, the entire disclosure of which is hereby incorporated by reference.[0002]The present invention relates generally to tube support plates of steam generators.BACKGROUND[0003]FIG. 1 shows a nuclear steam generator 52 which comprises a plurality of U-shaped tubes disposed within its shell to form tube bundles 50. Tube bundles 50 typically contain thousands of generator tubes. Tube sheets are provided for supporting the tubes at the ends opposite the U-shaped curvature. A primary fluid is heated in the reactor core through circulation and enters steam generator 52 through a primary inlet 54 fluid nozzle where it is distributed by upper tube sheet through the generator tubes and collected at the lower tube sheet. The fluid then flows through a primary fluid outlet 56 nozzle to the remainder of the reactor system. A feedwater stream is also introduced into steam generator 52 secondary...

AI Technical Summary

Benefits of technology

[0010]An object of the invention is to provide measured values from a bobbin eddy current examination of steam generator tubing to calculate the degree of flow restriction, “clogging,” or “blockage,” at each of the TSP flow regions, and subsequently,

Problems solved by technology

This deposition collects and builds up as sludge patches about broached openings of TSP 58, particularly on the free tube heat transfer surface which reduces the efficiency and the blockage within the support flow holes which acts as an impediment to the flow of feedwater and the water/steam mixture in the upper parts of the tube bundle as the water converts to steam.

This current practice requires unacceptable amounts of time and exposes personnel to large amounts of accumulated radioactive dose.

If a steam generator does not provide access ports for visual inspection tooling between each pair of TSP, the visual examination is limited to accessible areas for the uppermost TSP.

Consequently, a complete examination of the population of TSP flow regions is not possible and subsequent an

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